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Journal Articles

Levelized cost of electricity evaluation of SFR system considering safety measures

Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 10 Pages, 2019/05

The levelized cost of electricity is one of key indicator to evaluate economic competitiveness of energy systems. This report estimated the levelized cost of SFR system considering additional safety measures identified after the 1F incident and social cost, using major calculation tools: G4-ECONS and the calculation tool developed by the Governmental WG in Japan (CEWG-tool). The calculation results of G4-ECONS showed that the additional safety measures raise 160% of levelized cost in the case of the safety enhanced SFR system with 1500 MWe of twin looped cooling system. As a result of calculation with 3% discount rate and social cost, the levelized cost of the safety enhanced SFR system with 1200 MWe of Single looped cooling system was estimated 84 mills/kWh by CEWG-tool. This result is almost equal to the estimated levelized cost of similar standard LWR system, and it was indicated the economic competitiveness of the future SFR system.

Journal Articles

The Prospect of economics of fast reactor cycle

Mukaida, Kyoko; Kato, Atsushi; Kamiya, Masayoshi; Ishii, Katsunori

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 61(1), p.40 - 47, 2019/01

Japan Atomic Energy Agency has proceeded on the research and development (R&D) of fast neutron rector fuel cycle with a system which has economic competitiveness in contrast with light water reactor systems as one of development objectives, from the start of its development. This report shows the evaluation results of generation cost of fast reactor fuel cycle in light of additional safety measure cost and social cost, based on the design of fast reactor and related fuel cycle facilities which considered in FaCT phase I.

Journal Articles

Study of treatment scenarios for fuel debris removed from Fukushima Daiichi NPS

Washiya, Tadahiro; Yano, Kimihiko; Kaji, Naoya; Yamada, Seiya*; Kamiya, Masayoshi

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

On March 11, 2011, a severe nuclear accident occurred at Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Plant (hereinafter called as F1). After the accident, the Council for the Decommissioning was established, mainly by the government and TEPCO, and a road map for the F1 decommissioning was drawn up. In the road map, the fuel debris removal from the reactors is scheduled to launch around 2020. In this study, the characteristics and technological issues of each potential treatment scenario were extracted, and the scenarios were prioritized in advance of formal evaluations in the future. The preliminary evaluation results show that long term storage and direct disposal have more positive aspects in terms of economic efficiency and radioactive waste generation. On the other hand, stabilizing processing, aqueous processing, and pyrochemical processing have been estimated to have more disadvantages in such aspects.

Journal Articles

Experimental study on behavior of Cs in uranium crystallization of advanced aqueous reprocessing system with simulated dissolver solution

Shibata, Atsuhiro; Yano, Kimihiko; Kamiya, Masayoshi; Nakamura, Kazuhito; Washiya, Tadahiro; Chikazawa, Takahiro*; Kikuchi, Toshiaki*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 8(3), p.245 - 253, 2009/09

Behavior of Cs in U crystallization process of advanced aqueous reprocessing system was investigated with simulated dissolver solution. Beaker-scale U crystallization experiments were carried out with some simulated dissolver solutions. The results show that possibility of generation of CsNO$$_{3}$$,Cs$$_{2}$$UO$$_{2}$$ (NO$$_{3}$$)$$_{4}$$ or Cs-FP complex salt is small. Precipitation experiments of Cs-U(IV) complex salts were also carried out with nitrate solution of U(IV) and Cs. It was found that Cs-U(IV) complex salt was precipitated in higher acidity than 5 mol/dm$$^{-3}$$. It is suggested that Cs-Pu(IV) precipitates can be generated in the U crystallization process, under specific solution condition.

Journal Articles

Dissolution of powdered spent fuel and U crystallization from actual dissolver solution for "NEXT" process development

Nomura, Kazunori; Hinai, Hiroshi; Nakahara, Masaumi; Kaji, Naoya; Kamiya, Masayoshi; Oyama, Koichi; Sano, Yuichi; Washiya, Tadahiro; Komaki, Jun

Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 5 Pages, 2008/05

Journal Articles

Separation of actinide elements by solvent extraction using centrifugal contactors in the NEXT process

Nakahara, Masaumi; Sano, Yuichi; Koma, Yoshikazu; Kamiya, Masayoshi; Shibata, Atsuhiro; Koizumi, Tsutomu; Koyama, Tomozo

Journal of Nuclear Science and Technology, 44(3), p.373 - 381, 2007/03

 Times Cited Count:26 Percentile:86.4(Nuclear Science & Technology)

Actinides recovery was attempted by the simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery and the SETFICS process for Am and Cm recovery with a view to decreasing the environmental impact. Uranium, Pu and Np co-recovery was conducted under the condition with high nitric acid concentration in the feed solution or scrubbing solution. High nitric acid concentration in the feed solution availed to the Np oxidation not only in the feed solution, but also at the extraction section. This oxidation reaction permitted the Np extraction with U and Pu. In the SETFICS process, a TRUEX solvent of 0.2M CMPO/1.4M TBP was employed to increase the loading of metals. In place of sodium nitrate, HAN was applied to this experimental flow sheet for "salt-free" concept. This experiment was succeeded in Am and Cm product. On high-loading flow sheet, the flow rate of aqueous effluents and spent solvent was expected to decrease in 47% and 54%, respectively.

Journal Articles

Edge pedestal physics and its implications for ITER

Kamada, Yutaka; Leonard, A. W.*; Bateman, G.*; Becoulet, M.*; Chang, C. S.*; Eich, T.*; Evans, T. E.*; Groebner, R. J.*; Guzdar, P. N.*; Horton, L. D.*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

no abstracts in English

Journal Articles

Actinides recovery by solvent extraction in NEXT process

Nakahara, Masaumi; Sano, Yuichi; Koma, Yoshikazu; Kamiya, Masayoshi; Shibata, Atsuhiro; Koizumi, Tsutomu; Koyama, Tomozo

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10

Concerning the advanced aqueous reprocessing system named NEXT process, the behavior of actinide elements was investigated in main two extraction processes of NEXT process, i.e. the simplified PUREX process for U, Pu and Np recovery, and SETFICS process for Am and Cm recovery.

Journal Articles

Present Status of Advanced Aqueous Separation Process Technology Development

Koyama, Tomozo; Sano, Yuichi; Kamiya, Masayoshi; Shibata, Atsuhiro

Program and Abstracts, p.50, P. 50, 2005/02

Small scale hot tests have been conducted with irradiated fuel pins of the experimental Fat Reactor

Journal Articles

Direct Extraction of Uranium and Plutonium from Oxide Fuel using TBP-HNO$$_{3}$$Complex for Super-DIREX Process

Kamiya, Masayoshi; Miura, Sachiko; Nomura, Kazunori; Koyama, Tomozo; Ogumo, Shinya*; Mori, Yukihide*; Enokida, Yoichi*

CD-ROM, P1-35, 4P., 4 Pages, 2004/00

Super-DIREX is a new reprocessing method which has high economical efficiency. Experimental study of this process was started on the direct extraction of U and Pu from irradiated MOX fuel by the supercritical carbon dioxide (SFCO$$_{2}$$) containing TBP-HNO$$_{3}$$ complex. This report describes direct extraction of U and Pu with TBP-HNO3 complex at atmospheric pressure, as the first test for irradiated fuel, in order to investigate the applicability of SFCO$$_{2}$$ containing TBP-HNO$$_{3}$$ complex. In this test, dependency on dissolution temperature, Pu content, fuel/ TBP-HNO$$_{3}$$ complex ratio and effect of voloxidation were investigated. From these results, TBP-HNO$$_{3}$$ complex was found to be effective in the respect of the recovery of U and Pu. The number of the process step in dissolution and co-extraction is small, and amount of waste can be reduced. It is applicable to the direct extraction in Super-DIREX.

Journal Articles

Conceptual Design Study on Advanced Aqueous Reprocessing System for Fast Reactor Fuel Cycle

Takata, Takeshi; Koma, Yoshikazu; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori; Ogino, Hideki; Koyama, Tomozo; Aose, Shinichi

Journal of Nuclear Science and Technology, 41(3), 307 Pages, 2004/00

 Times Cited Count:27 Percentile:85.48(Nuclear Science & Technology)

The design study of aqueous reprocessing system has been progressed for the feasibility study on commercialized fast reactor cycle systems. Based on the PUREX process,an aqueous reprocessing process with the addition of a uranium crystallization step and

JAEA Reports

TECHNICAL STUDY REPORT ON REPROCESSING SYSTEMS, Investigation on Alternatives for Advanced Aqueous Reprocessing System

Koma, Yoshikazu; Takata, Takeshi; Kamiya, Masayoshi; Sato, Koji

JNC TN9410 2003-010, 112 Pages, 2003/12

JNC-TN9410-2003-010.pdf:4.73MB

This report summarizes the design work made bay the reprocessing Technoplogy Group in 2002 FYJ and includes the followings: advanced aqueous reprocesing, supercritical liquid direct extraction as an alternative, Am and Cm recovery and FP recovery.

Journal Articles

High performance tokamak experiments with a ferritic steel wall on JFT-2M

Tsuzuki, Kazuhiro; Kimura, Haruyuki; Kawashima, Hisato; Sato, Masayasu; Kamiya, Kensaku; Shinohara, Koji; Ogawa, Hiroaki; Hoshino, Katsumichi; Bakhtiari, M.; Kasai, Satoshi; et al.

Nuclear Fusion, 43(10), p.1288 - 1293, 2003/10

 Times Cited Count:39 Percentile:76.12(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Extraction of Uranium and Plutonium from Irradiated Fuel in Super-DIREX Reprocessing Method

Miura, Sachiko; Kamiya, Masayoshi; Nomura, Kazunori; Miyachi, Shigehiko; Koyama, Tomozo; Ogumo, Shinya*; Shimada, Takashi*

Abstracts P.30, 30 Pages, 2003/00

None

Journal Articles

Conceptual Design Study on Advaanced Aqueous Reprocessing Sysrwm for FR Fuel Cycle

; ; Sato, Koji; Kamiya, Masayoshi; Shibata, Atsuhiro; Nomura, Kazunori

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), P. P380, 2003/00

None

JAEA Reports

None

Kamiya, Masayoshi; Ojima, Hisao; Shinoda, Yoshihiko

PNC TN8410 98-050, 157 Pages, 1998/03

PNC-TN8410-98-050.pdf:7.3MB

None

Journal Articles

System Study on the Advanced Fuel Recycle

Ojima, Hisao; *; *; Kamiya, Masayoshi*

Proceedings of International Conference on Future Nuclear Systems (GLOBAL'97), 0 Pages, 1997/00

None

Oral presentation

Plutonium and other actinides behaviour in NEXT process

Miura, Sachiko; Nakahara, Masaumi; Sano, Yuichi; Kamiya, Masayoshi; Nomura, Kazunori; Komaki, Jun

no journal, , 

The behaviour of Pu and other actinides in the crystallization process and U-Pu-Np co-recovery process was discussed. Pu showed the different behaviour in the crystallization process according to its valence in the dissolver solution. Low DF of Cs in some crystallization conditions might be related with the formation of some kinds of Cs compounds with Pu in the dissolver solution. In the U-Pu-Np co-recovery process, Although there are some considerable points, e.g. temperature control in the stripping section, suitable condition for Np extraction, etc., we confirmed that it was possible to co-recover U-Pu-Np under the appropriate condition.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid; System outline and development plan

Kamiya, Masayoshi; Koyama, Tomozo; Aoki, Kazuo*; Sawada, Kayo*

no journal, , 

no abstracts in English

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 2; Distribution coefficient of Am in U/Pu/Am system

Kamiya, Masayoshi; Koyama, Tomozo; Miura, Sachiko; Aoki, Kazuo*; Sawada, Kayo*

no journal, , 

Distribution coefficient of Am and relation between distribution coefficient of Am and concentration of nitric ion in high salt concentration and high acid concentration region, were given by the experiment using U, Pu, and Am nitric acid solution. The Extractant of this experiment is TBP.

34 (Records 1-20 displayed on this page)